ML20138A299

Forwards Crdr Final Rept,Per NUREG-0737,Suppl 1,Section 5, Detailed Crdr. Numerous Enhancements Planned for Control Room Panels,Instrumentation & Annunciators.Improvements of Greatest Benefit Will Be Implemented Early

ML20138A299
Person / Time
Site:	Peach Bottom
Issue date:	02/26/1986
From:	Daltroff S PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	Muller D Office of Nuclear Reactor Regulation
Shared Package
ML20138A304	List: ML20138A299 ML20138A322
References
RTR-NUREG-0737, RTR-NUREG-737 NUDOCS 8603140191
Download: ML20138A299 (4)

Text

___.

PHILADELPHIA ELECTRIC COMPANY 2301 M ARKET STREET F).O. BOX 8699 PHILADELPHIA. PA.19101

• ]E,s =;i,Sh[ February 26, 1986 Docket No. 50-277 50-278 Mr. Daniel R. Muller, Director BWR Project Directorate #2

Division of Boiling Water Reactor Licensing

U.S. Nuclear Regulatory Commission Washington, D.C. 20555

SUBJECT:

Peach Bottom Atomic Power Station NUREG-0737, Supplement 1, Section 5 Control Room Design Review I

Reference:

(1) Correspondence dated April 15, 1983 l S. L. Daltroff, PECo to D. G. Eisenhut, NRC l

l (2) Correspondence dated September 14, 1983

J. W. Gallagher, PECo to D. G. Eisenhut, NRC (3) Correspondence dated October 31, 1983 S. L. Daltroff, PECo to D. E. Eisenhut, NRC (4) Correspondence dated January 7, 1985 S. L. Daltroff, PECo to J. F. Stolz, NRC (5) Correspondence dated May 22, 1985 S. L. Daltroff, PECo to J. F. Stolz, NRC

Dear Mr. Muller:

E A Attached is a copy of the Peach Bottom Control Room Design Review Final Report, submitted in accordance with the o commitments of the reference correspondence and the requirements

. of NUREG-0737, Supplement 1, Section 5, Detailed Control Room

& Design Review. The report identifies numerous enhancements O, planned for the control room panels, instrumentation, and g annunciators.

f'N" The proposed enhancements are the result of a Control Room Design Review (CRDR) and evaluation program that has been in b

I -_ w

Mr. Daniel R. Mullcr, Dircctor F brunry 26, 1986 Page 2 progress for more than five years using the human factor engineering guidance provided in the BWR Owners Group CRDR Survey Program. In parallel with this ef fort, several improvements in the control roon design have already been implemented in response to the recognized need for more attention to human f actor engineering concepts. The enhancements completed include improvements in control room lighting, desk arrangement, noise levels, and annunciator performance. Further, the human factor concepts applied to the proposed enhancements have been incorporated in the recently installed control panel for the new of fgas system. As the modifications associated with the enhancements are subjected to the rigorous review process required by the administrative controls in section 6 of the Technical Specifications, and 10CFR 50.59, some revisions in the enhancements as described in the report will likely occur, including deletions and additions. The NRC will be kept informed of these revisions in the progress reports described below.

I The enhancements described in the report that do not I require a plant outage will be implemented over the next two years. Those enhancements for which a plant outage is necessary to avoid operating risks will be implemented during the next several refueling outages on each unit in accordance with a living schedule approach that recognizes all the outage activity needs of the plants. The NRC will be kept informed of the implementation status of control room enhancements in the annual progress report described below. Those improvements providing the greatest benefit will be considered for early implementation.

A progress report will be submitted within two months following completion of the next refueling outage (Unit 2 - starting January 1987) and annually thereafter until the control room improvement task is complete. The report wi'll summarize activities completed, and any revisions in the planned enhancements or implementation schedule.

Should you have any questions regarding this submittal, please do not hesitate to contact us.

Very truly ours, ,

,5  ; f WCB vdw Attachments cc: Dr. T. E. Murley, Administrator, Region 1, USNRC (w/o attachments)

T. P. Johnson, Resident Site Inspector (w/o attachments)

. - -- - . ~. -. . . . . . . .. .- -. . - . . . . - - -

.o- *.

+

PHILADELPHIA ELECTRIC COMPANY 2301 MARKET STREET P.O. BOX 8699 PHILADELPHIA PA.19101 sMitLos L. DALTnorr (2151 841 5001 l "l,;" g h February 26, 1986 i

Docket No. 50-277

. .__. ~ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .__. _ _ _ _ _ _ . . . . - -

50-278 - ~

Mr.' Daniel R. Muller, Director BWR Project Directorate #2 . _

Division of Boiling Water Reactor Licensing '

U.S. Nuclear Regulatory Commission Washington, D.C. 20555 i

SUBJECT:

Peach Bottom Atomic Power Station NUREG-0737, Supplement 1, Section 5 Control Room Design Review Reference (1) Correspondence dated April 15, 1983 S. L. Daltroff, PECo to D. G. Eisenhut, NRC i

(2) Correspondence dated September 14, 1983  :

J. W..Gallagher, PEco to D.,G. Eisenhut, NRC l

4 (3) Correspondence dated October 31, 1983  ;

}; S. L. Daltroff, PECo to D. E. A senhut, NRC N.5; c.-

J (4) Correspondence dated January 7, 1985 *,-

S. L. Daltroff, PEco to J. F. Stolz, NRC ,

(5) Correspondence dated May 22, 1985 i -

S. L. Daltroff, PECo to J. F. Stolz, NRC i

Dear Mr. Muller  ;

Attached is a copy of the Peach Bottom Control Room Design Review Final Report, submitted in accordance with the  ;

commitments of the reference correspondence and the requirements

-of NUREG-0737, Supplement 1, Section 5, Detailed Control Room l Design Review. The report identifies numerous enhancements l planned for the control room panels, instrumentation, and annunciators.

The proposed enhancements are the result of a Control

. Room Design Review (CRDR) and evaluation program that has been in 1

,1 t

Mr. D1niel R. Muller, Director February 26, 1986

, Page 2 progress for more than five yea. s using the human factor engineering guidance provided in che BWR Owners Group CRDR Survey Program. . In parallel with this e~f fort, several improvements in the control room design have already been implemented in response to the recognized need for more attention to human factor ,

engineering concepts. The enhancements completed include ,

improvements in control.. room lighting, desk arrangement, noise

___ _ levels,.and annunciator performance. . Fur ther, the human factor.

concepts applied to the proposed enhancements have been incorporated in the recently idstalled control panel for the new offgas system. As the modifications associated with the enhancements are subjected to the rigorous review process' required by the administrative controls in section 6 of the Technical Specifications, and 10CFR 50.59, some revisions in the <

enhancements as described in the report will likely occur, including deletions and additions. The NRC will be kept informed of these revisions in the progress reports described below.

The enhancements described in the report that do not require a plant outage will be . implemented over the next two years. Those enhancements for which a plant outage is necessary to avoid operating risks will be' implemented during the next several refueling outages on each' unit in accordance with a

'living schedule approach that recognizes all the outage activity needs of the plants. The NRC will be kept informed of the implementation status of centrol room enhancements in the annual progress report described below. Those improvements providing the greatest benefit will be considered for early implementation.

A progress report will be submitted within two months following completion of the next refueling outage (Unit 2 - starting January 1987) 'and annually thereaf ter until the control room improvement task is complete. The report will summarize Q acs,ivities completed, and any revfilcas in the planned enhancements or implementation ;W 69 te.

Should you have any qcerti..e regarding this submittal, please do not hesitate to contact us.

V F

Very truly ours, .

)

'd s v -

• Wl W_

WCB vdw Attachments l

cc Dr. T. E. Murley, Administrator, Region I, USNRC (w/o attachments) l T. P. ' Johnson, Resident Site Inspector (w/o attachments) l

'